ML18151A664
| ML18151A664 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/06/1999 |
| From: | Clemens C, Hofmann M, Lawrence D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18151A665 | List: |
| References | |
| NE-1206, NE-1206-R00, NUDOCS 9908240207 | |
| Download: ML18151A664 (57) | |
Text
-NOTICE-THE ATTACHED FILES ARE OFFICAL RECORDS OF THE' OCIO/INFORMATION MANAGEMENt DIVISION. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS AND ARCHIVES SERVICES SECTION, T-5C3. PLEASE DO NOT SEND DOCUMENTS ,
CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S)
FROM DOCUMENTS FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.
-NOTICE~
'I TECHNICAL REPORT NE-1206 - REV. 0 SURRY UNIT 2, CYCLE 16 STARTUP PHYSICS TESTS REPORT NUCLEAR ANALYSIS AND FUEL NUCLEAR ENGINEERING & SERVICES VIRGINIA POWER AUGUST 1999 PREPAREDBY: 1'~4- ~ 'lP,'Yf1 7 C. D. Clemens Date REVIEWED BY: ~ A - ~ 7/z<t/"19 M. A. Ho ann Date REVlliWEDBY: [~~
APPROVED BY: ~£.
~
~fa~
Date QA Category: Nuclear Safety Related Keywords: S2Cl6, Startup
., CLASSIFICATION/DISCLAIMER The data, techniques, information, and conclusions in this report have been prepared solely for use by Virginia Electric and Power Company (the Company), and they may not be appropriate for use in situations other than those for which they have been specifically prepared. T_he Company therefore makes no claim or warranty whatsoever, express or implied, as to their accuracy, usefulness, or applicability. In particular, THE COMPANY MAKES NO WARRANTY OF MERCHANTABILITY OR FITNESS FOR A PARTICULAR PURPOSE, NOR SHALL ANY WARRANTY BE DEEMED TO ARISE FROM COURSE OF DEALING OR USAGE OF TRADE, with respect to this report or any of the data, techniques, information, or conclusions in it. By making this report available, the Company does not authorize its use by others, and any such use is expressly forbidden except with the prior written approval of the Company. Any such written approval shall itself be deemed to incorporate the disclaimers of liability and disclaimers of warranties provided herein. In no event shall the Company be liable, under any legal theory whatsoever (whether contract, tort; warranty, or strict or absolute liability), fot any property damage, mental or physical injury or death, loss of use of property, or other damage resulting from or arising out of the use, authorized or unauthorized, of this report or the data, techniques, information, or conclusions in it.
NE-1206 S2C16 Startup Physics Tests Report Page 1 of 55
TABLE OF CONTENTS PAGE Classification/Disclaimer............................................................................. 1 Table of Contents......................................................................................... 2 List of Tables ......................................................................... :..................... 3 List of Figures.............................................................................................. 4 Preface......................................................................................................... 5 Section 1 Introduction and Summary....................................................... 6 Section 2 Control Rod Drop Time Measurements.................................. 15 Section 3 Control Rod Bank Worth Measurements................................ 20 Section 4 Boron Endpoint and Worth Measurements............................. 25 Section 5 Temperature Coefficient Measurement................................... 29 Section 6 Power Distribution Measurements.......................................... 31 Section 7 References................................................................................ 38 APPENDIX Startup Physics Test Results and Evaluation Sheets.......... 39 NE-1206 S2C16 Startup Physics Tests Report Page 2 of 55
LIST OFTABLES TABLE TITLE PAGE 1.1 Chronology of Tests............................................................................. . 9 2.1 Hot Rod Drop Time Summary............................................................. 17 3.1 Control Rod Bank Worth Summary..................................................... 22 4.1 Bon;m Endpoints Summary.................................................................. 27 4.2 Boron Worth Coefficient..................................................................... 28 5.1 Isothermal Temperature Coefficient Summary.................................... 30 6.1 Incore Flux Map Summary.................................................................. 33 6.2 Comparison of Measured Power Distribution Parameters With Their Core Operating Limits....................................................... 34 NE-1206 S2C16 Startup Physics Tests Report Page 3 of 55
LIST OF FIGURES FIGURE TITLE PAGE 1.1 Core Loading Map............................................................................... 10 1.2 Beginning of Cycle Fuel Assembly Bumups...................................... 11 1.3 In core Thimble Locations. . . . . . . . . . . . . . . . . . . . . . . . .................................... 12 1.4 Burnable Poison Assembly Locations...... . . . . . . . . . .... ..... ..... ... ... ..... .... 13 1.5 Control Rod Locations........................................................................ 14 2.1 Typical Rod Drop Trace ............................................... ~...................... 18 2.2 Rod Drop Time - Hot Full Flow Conditions....................................... 19 3.1 Control Bank B Integral Rod Worth - HZP......................................... 23 3.2 Control Bank B Differential Rod Worth - HZP .................................. 24 6.1 Assemblywise Power Distribution - 23% Power................................ 35 6.2 Assemblywise Power Distribution - 65% Power................................ 36 6.3 Assemblywise Power Distribution -100% Power............................... 37 NE-1206 S2C16 Startup Physics Tests Report Page 4 of 55
PREFACE This report presents the analysis and evaluation of the physics tests which were performed to* verify that the Surry Unit 2, Cycle 16 core could be operated safely, and makes an initial evaluation of the performance of the core. It is not the intent of this report to discuss the particular methods of testing or to present the detailed data taken.
Standard testing techniques and methods of data analysis were used. The test data, results and evaluations, together with the detailed startup procedures, are on file at the Surry Power Station. Therefore, only a cursory discussion of these items is included in this report. The analyses presented include a brief summary of each test, a comparison: of the test results with design predictions, and an evaluation of the results.
The Surry Unit 2, Cycle 16 startup physics tests results and evaluation sheets are included as an appendix* to provide additional information on the startup test results.
Each data sheet provides the following information: 1) test identification, 2)
- test conditions (design), 3) test conditions (actual), 4) test results, 5) acceptance criteria, and
- 6) comments concerning the test. These sheets provide a compact summary of the startup test results in a consistent format. The design test conditions and design values (at design conditions) of the. measured parameters were completed prior to the startup physics testing. The entries for the design values were based on the calculations performed by Virginia Electric and Power Company's Nuclear Analysis and Fuel Group 1* During the tests, the data sheets were used as _guidelines both to verify that the proper test conditions were met and to facilitate the preliminary comparison between measured and predicted test results~ thus enabling a quick identification of possible problems occurring during the tests.
NE-1206 S2C16 Startup Physics Tests Report Page 5 of 55
f.
SECTION 1 INTRODUCTION*AND
SUMMARY
On April 18, 1999 Unit No. 2 of the Surry Power Station shutdown for its fifteenth refueling. During this shutdown, 73 of the 157 fuel assemblies in the core were replaced with 57 fresh assemblies, 12 twice-burned assemblies, and 4 thrice-burned assemblies. .The Cycle 16 core consists of 9 sub-batches of fuel: two once-burned batches from Cycle 15 (batches 17A and 17B); three twice-burned batches, two batches from Cycle 15 (batches 16A and 16B) and one batch from Cycle 13 (batch 14B); two thrice-burned batches, one batch from Cycle 15 (batch 15B) and one batch from Cycle 14 (batch 14B); and three fresh batches (batches 18A, 18B, and 18C).
The core loading pattern and the* design parameters for each sub-batch are shown in Figure 1.1. Beginning of cycle fuel assembly burnups are given in Figure 1.2. The available incore thimble locations used for the flux map analyses during startup physics testing are ic;lentified in Figure 1.3. Figure 1.4 identifies the location and number of burnable poison rods for Cycle 16, while Figure 1.5 identifies control rod locations in the Cycle 16 core.
NE-1206 S2C16 Startup Physics Tests Report Page 6 of 55
Tfu.e Cycle 16 core achieved initial criticality at 12:21 on May 25, 1999. Prior to and following criticality, startup physics tests were performed as outlined in Table 1.1. A summary of the results of these tests follows:
- 1. The measured drop time of each control rod was within the 2.4 second limit of Technical Specification 3.12.C.l.
- 2. Individual control rod bank worths were measured using the rod swap technique 2*5
- The sum of the individual measured control rod bank worths was within 1.1 % of the design prediction and the reference bank worth was within 2.4% of its d~sign prediction. The other control rod banks were within 3.9% or 34 pcm of the design predictions. These results are within the design tolerances of +/-15% for individual banks worth more than 600 pcm (+/-10% for the rod swap reference bank worth), +/-lQO pcm for individual banks worth 600 pcm or less, and +/-10% for the sum of the individual control rod bank worths.
- 3. Measured critical boron concentrations for two control bank configurations (B bank in and ARO) were within 14 ppm of the design predictions. These results were within design tolerances and met the Technical Specification 4.1 O.A criterion that the overall core reactivity balance shall be within +/-1 % Afc/k of the design prediction.
- 4. The boron worth coefficient measurement was within 5.9% of the design prediction, which is within the design tolerance of +/-10%.
NE-1206 S2C16 Startup Physics Tests Report Page 7 of 55
- 5. The measured isothermal temperature coefficient (ITC) for the all-rods-(Jut (ARO) configuration was within 1.69 pcml°F of the design prediction. This result is within the design tolerance of +/-3 pcml°F. The measured ITC of -1.05 pcml°F meets the Core Operating Limits Report (COLR)8.4 2.1.1 criterion that the moderator temperature coefficient (MTC) be less than or equal to +6.0 pcml°F. When the Doppler temperature coefficient (-1.70 pcm/ °F) and a 0.5 pcml°F uncertainty are accounted for in the MTC limit, the MTC requirement is satisfied as long as the ITC is less than or equal to +3.80 pcml°F.
- 6. Measured core power distributions were within established acceptance criteria and COLR8.4 limits. The average relative assembly power distribution measured/predicted percent difference was 2.2% or less for the three initial power ascension flux maps. The heat flux hot channel factors, F-Q(Z), and enthalpy rise hot channel factors, F-DH(N),
were within the limits of COLR Sections 2.3 and 2.4, respectively.
In summary, all startup physics test results were acceptable. Detailed results, specific design tolerances, and acceptance criteria for each measurement are presented in the following sections of this report.
NE-1206 S2C16 Startup Physics Tests Report Page 8 of 55
Table 1.1 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS CHRONOLOGY OF TESTS Reference Test Date Time Power Procedure Hot Rod Drop-Hot Full Flow 5/23/99 1500 HSD 2-NPT-RX-014 Zero Power Testing Range 5/25/99 1310 HZP 2-NPT-RX-008 Reactivity* Computer Checkout 5/25/99 . 1330 HZP 2-NPT-RX-008 Boron Endpoint - ARO 5/25/99 1600 HZP 2-NPT-RX-008 Temperature Coefficient - ARO 5/25/99 1719 HZP 2-NPT-'RX-Oos***
BankB Worth 5/25/99 2014 HZP 2-NPT-RX-008 Boron Endpoint - B in 5/25/99 2300 HZP 2-NPT-RX-008 Bank D Worth - Rod Swap 5/26/99 0012 HZP . 2-NPT-RX-008 Bank C Worth - Rog Swap 5/26/99 0054 HZP 2-NPT-RX-008 Bank A Worth - Rod Swap 5/26/99 0135 HZP 2-NPT-RX-008 Bank SB Worth - Rod Swap
- 5/26/99 0221 *HZP 2-NPT-RX-008 Bank SA Worth-Rod Swap 5/26/99 0305 HZP 2-NPT-RX-008 Flux Map - 22.9% Power 5/30/99 1251 22.9% 2-NPT-RX~008 Peaking Factor Verification 2-NPT-RX-002
& Power Range Calibration Flux Map - 65.3% Power 5/31/99 2034 65.3% 2-NPT-RX-008 Peaking Factor Verification 2-NPT-RX-002
& Power Range Calibration Flux Map - 100% Power 6/18/99 0900 100% 2-NPT-RX-008 .
Peaking Factor Verification 2-NPT-RX-002
& Power Range Calibration NE-1206 S2C16 Startup Physics Tests Report Page 9 of 55
Figure I.I SURRY UNIT 2 - CYCLE 16 CORE LOADING MAP R p *N M L K J H G F E D C B A 15B 15B 15B 5X3 3X5 3X4 14B 16A 18C 16B 18C 16A 14B 6W7 1Y2 31N 3Y9 34N OY4 5W7 2 14B 18B I8C 17A I8C 17A I8C 18B 14B 5W3 19N 36N 3IL 43N 19L 47N 17N 4W4 3 14B 16B 18C 17A 18B 17B 18B I7A 18C 16B 14B 3W8 3Y7 53N ISL ION 45L 25N 20L 52N SYS 5W4 4 I4B 18B 18C 17A 18B 17A 18B 17A 18B 17A 18C 18B 14B 3W7 04N 40N 21L 16N 06L 20N IOL 13N 23L 35N 05N 3W4 5 16A 18C 17A 18B 17B 17B 17A 17B I7B 18B 17A 18C 16A 2Y5 32N 30L 28N 41L 33L 04L 40L 56L 15N 13L 41N 3YO 6 15B I8C 17A 18B 17A 17B 17B 17B 17B 17B 17A 18B 17A 18C 15B 5X2 46N 03L 08N 25L 47L 53L 55L 42L 37L 32L 24N OIL 55N 3XO 7 15B 16B 18C 17B 18B 17A 17B 18A 17B I7A 18B 17B 18C 16B 15B 5X5 3Y6 38N 46L 26N 09L 39L OIN SOL I6L 12N 54L 30N 5Y9 4XO 8 16B 18C I7A 18B 17A 17B 17B 17B 17B 17B 17A 18B 17A 18C 15B 4Y3 42N 26L 21N 18L 34L 49L 48L 44L 43L 08L 18N 05L 39N 4X8 9 16A 18C 17A 18B 17B 17B 17A 17B 17B 18B 17A I8C 16A IYl 45N 22L 06N 36L SIL 02L 35L 52L 29N I7L 48N OY7 10 14B 18B 18C 17A 18B 17A 18B 17A 18B 17A 18C 18B 14B 4W2 22N SON 12L IIN 27L 07N 24L 14N llL 33N 09N 4W5 *11 14B 16B I8C 17A 18B 17B 18B 17A 18C 16B 14B 3W3 3Y4 49N 07L 23N 38L 02N 28L 54N 3Y8 3W5 12 14B 18B 18C 17A 18C 17A 18C 18B 14B 4W6 27N 44N 14L SIN 29L 37N 03N 3W9 13 14B 16A 18C 16B 18C 16A 14B D ===>Batch
===> Assembly ID 5W9 2Yl 56N 15B 4X6 4YO 15B 4X2 57N 15B 3X3 2Y8 5W5 14 15 FUEL ASSEMBLY DESIGN PARAMETERS SUB-BATCH 14B 15B 16A 16B 17A 17B 18A 18B 18C INITIAL ENRICHMENT 4.0050 4.0114 3.7970 4.0060 3.9038 4.0612 3.8272 4.1015 4.2560 (W/0 U-235)
BURNUP AT BOC 16 40400 43149 41044 36195 23329 21024 0 0 0 (MWD/MTU)
ASSEMBLY TYPE 15xl5 15xl5 15xl5 15xl5 15xl5 15x15 15xl5 15xl5 15xl5 NUMBER OF ASSEMBLIES 16 11 8 9 32 24 1 28 28 FUEL RODS PER 204 204 204 204 204 204 204 204 204 ASSEMBLY NE-1206 S2C16 Startup Physics Tests Report Page 10 of 55
Figure 1.2 SURRY UNIT 2 - CYCLE 16 BEGINNING OF CYCLE FUEL ASSEMBLY BURNUPS R p N M L K J H *o F E D C B A
- 5X3 3X5 3X4 43454 42515 43517 6W7 1Y2 31N 3Y9 34N OY4 5W7 41359 40885 0 34616 0 40811 41168 2 5W3 19N 36N 3IL 43N 19L 47N 17N 4W4 39429 0 0 19034 0 19206 0 0 39539 3 3W8 3Y7 53N 15L ION 45L 25N 20L 52N 5Y5 5W4 40166 35512 0 25368 0 22331 0 25087 0 35506 39317 4 3W7 04N 40N 21L 16N 06L 20N lOL 13N 23L 35N 05N 3W4 40820 0 0 24662 0 24457 0 24623 0 24273 0 0 40986 **- 5 2Y5 32N 30L 28N 41L 33L 04L 40L 56L 15N 13L 41N 3YO 41344 0 25072 0 24117 17400 24533 17707 23357 0 25125 0 40984 6 5X2 46N 03L 08N 25L 47L 53L 55L 42L 37L 32L 24N OIL 55N 3XO 43468 0 19892 0 24230 17129 23574 21769 23341 17477 23941 0 19121 0 43748 7 5X5 3Y6 38N 46L 26N 09L 39L OlN 50L 16L 12N 54L 30N 5Y9 4XO 41882 34268 0 21440 0 24361 21770 0 22522 24665 0 21818 0 34396 42457 8 4Y3 42N 26L 21N 18L 34L 49L 48L 44L 43L 08L 18N 05L 39N 4X8 43117 0 19235 0 24164 17155 23599 21540 22803 17654 24663 0 19133 0 43743 9 lYl 45N 22L 06N 36L 51L 02L 35L 52L 29N 17L 48N OY7 40893 0 25255 0 23208 17322 24469 17284 23285 0 25121 0 40387 10 4W2 22N 50N 12L 1lN 27L 07N 24L 14N 1lL 33N 09N 4W5 40923 0 0 24438 0 23883 0 24324 0 24576 0 0 40689 11 3W3 3Y4 49N 07L 23N 38L 02N 28L 54N 3Y8 3W5 38884 35711 0 25157 0 21922 0 24952 0 35756 39065 12
- 4W6 27N 44N 14L 51N 29L 37N 03N 3W9 39850 0 0 19579 0 18975 0 0 38602 13 5W9 2Yl 56N 4YO 57N 2Y8 5W5 40744 41168 0 34778 0 40467 40698 14 4X6 4X2 3X3 43908 42674 44577 15 D ==> Assembly ID
==> Assembly Burnup (MWD/MTU)
NE-1206 S2C16 Startup Physics Tests Report Page 11 of 55
Figure 1.3 SURRY UNIT 2- CYCLE 16 INCORE THIMBLE LOCATIONS R p N M L K J H G F E D C B A IT*
IT 2 IT IT IT IT 3 IT IT IT 4 IT* IT IT* IT* IT IT 5 IT** IT IT 6 IT IT IT IT IT** 7 IT* IT IT IT IT IT 8 IT IT IT IT 9 IT IT IT IT 10 IT IT IT IT 11 IT IT IT IT 12 IT IT 13 IT IT* 14 IT** 15 IT - Incore Thimble
- - Unavailable Location For All Maps
- - Unavailable.Location For-Map 1 NE-1206 S2C16 Startup Physics Tests Report Page 12 of 55
Figure 1.4 SURRY UNIT 2-CYCLE 16 BURNABLE POISON ASSEMBLY LOCATIONS R p N M L K J H G F E D C B A 2
5P 20P 20P 20P 5P BP724 BP708 BP697 BP714 BP725 3 20P 20P 20P 20P BP718 BP694 BP687 BP721 4 5P 20P 20P 20P 20P 20P 5P BP726 BP720 BP700 . BP684 BP704 BP716 BP730 **-~ 5 20P 20P 20P 20P BP7IO BP705 BP701 BP715 6 20P 20P BP685 BP690 7 20P 20P 20P 20P 20P BP698 BP688 BP683 BP695 BP696 8 20P 20P BP693 BP692 9 20P 20P 20P 20P BP713 BP707 BP702 BP711 . -- 10 5P 20P 20P 20P 20P 20P 5P BP727 BP723 BP706 BP691 BP703 BP719 BP731 11 20P 20P 20P 20P BP722 BP689 BP686 BP717 12 5P 20P 20P 20P 5P BP728 BP712 BP699 BP709 BP729 13 14 15 5P - 5 Burnable Poison Rod Cluster 20P - 20 Burnable Poison Rod Cluster xxP 1-_ # of BP Rods
~-B_P#_#_#_~. BP Assembly ID NE-1206 S2C16 Startup Physics Tests Report Page 13 of 55
Figure 1.5 SURRY UNIT 2 - CYCLE 16 CONTROL ROD LOCATIONS R p N M L K J H G F E D C B A A D A 2 SA SA 3 C B B C 4 SB SB 5 A B D C D B A 6 SA SB SB SA *7 D C C D 8 SA SB SB SA 9 A B D C D B A IO SB SB 11 C B B C 12 SA SA 13 Absorber Material A D A 14 Ag-In-Cd 15 Function Number of Clusters Control Bank D 8 Control Bank C 8 Control Bank B 8 Control Bank A 8 Shutdown Bank SB 8 Shutdown Bank SA 8 NE-1206 S2C16 Startup Physics Tests Report Page 14 of 55
SECTI0N2 CONTROL ROD DROP TIME MEASUREMENTS The drop time of each control rod was measured at hot full-flow reactor coolant system (RCS) conditions (Tavg of 547 +/- 5°F) in order to verify that the time from initiation of the rod drop to the entry of the rod into the dashpot was less than or equal to the maximum allowed by Technical Specification 3.12.C.l.
The rod drop times were measured by withdrawing all banks to their fully withdrawn position and dropping all 48 control rods by opening the reactor trip breakers.
This allowed the rods to drop into the core as they would during a plant trip. The Individual Rod Position Indication (IRPI) primary coil voltage signals were recorded to determine the drop time of each rod.
As shown on the sample rod drop trace in Figure 2-,1, the initiation of the rod drop is indicated by the increase of the IRPI coil voltage. As the rod drops, a voltage is induced in the IRPI primary coil. The magnitude of this voltage is a function of control rod velocity. As the rod enters the dashpot region of the guide tube, its velocity slows causing.a.:v.oltage..decrease.in-theJRPI coil. -This .v.oltage ..reaches a minimum when the rod reaches the bottom of the dashpot. Subsequent variations in the trace are caused by rod bouncing.
NE-1206 S2C16 Startup Physics Tests Report Page 15 of 55
The measured drop times for each control rod are recorded on Figure 2.2. The slowest, fastest, and average drop times are summarized in Table 2.1. Technical Specification "3.12.C.1 specifies a maximum rod drop time from loss of stationary gripper coil voltage to dashpot entry of 2.4 seconds with the RCS at hot, full flow conditions.
These test results satisfied this limit. In addition, rod bounce was observed at the end of each trace which demonstrated that no control rod stuck in the -dashpot region.
NE-1206 S2C16 Startup Physics Tests Report Page 16 of 55
Table 2.1 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS HOT ROD DROP TIME
SUMMARY
ROD DROP TIME TO DASHPOT ENTRY SLOWEST ROD FASTEST ROD AVERAGE TIME F-06 1.41 sec. P-10* 1.26 sec. 1.30 sec.
- Rods M-12 and M-4 also had drop times of 1.26 sec.
NE-1206 S2C16 Startup Physics Tests Report Page 17 of 55
Figure 2.1 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS TYPICAL ROD DROP TRACE ROD DROP TIME MEASUREMENT 0.000 0.500 1.000 1.500 2.000 2.500 3.000 3.500 4.000 Time D:~D2000\S2C16_-1'C8A8.llW sec NE-1206 S2Cl6 Startup Physics Tests Report Page 18 of 55
Figure 2.2 SURRY UNIT 2-CYCLE 16 STARTUP PHYSICS TESTS ROD DROP TIME - HOT FULL FLOW CONDITIONS R p N M L K J H G F E D C B A 1.29 1.30 1.28 2 1.27 1.30 3 1.26 1.28 1.29 1.29 4 1.28 1.32 5 1.27 1.28 1.30 1.33 1.41 1.29 1.34 6 1.31 1.29 1.28 1.31 7 1.27 1.30 1.30 1.30 8 1.30 1.30 1.29 1.31 9 1.26 1.29 1.31 1.29 1.32 1.28 1.29 10 1.28 1.30 11 1.26 1.27 1.30 1.30 12 1.29 1.33 13 1.33 1.28 1.30 14 15 Q ===> Rod drop time*to dashpot entry (sec.)
NE-1206 S2C16 Startup Physics Tests Report Page 19 of 55
SECTION 3 CONTROL ROD BANK WORTH MEASUREMENTS Control rod bank worths were measured for the control and shutdown banks using the rod swap technique 2*5 . The initial step of the rod swap method diluted the predicted most reactive control rod bank (hereafter referred to as the reference bank) into the core and measured its reactivity worth using conventional test techniques. The reactivity changes resulting from the reference bank movements were recorded continuously by the reactivity computer and were used to determine the differential and integral worth of the reference bank. For Cycle 16, Control Bank B was used as the reference bank.
After the completion of the reference bank reactivity worth measurement, the reactor coolant system temperature and boron concentration were stabilized with the reactor near critical and the reference bank fully inserted. Initial statepoint data for the rod swap maneuver was obtained by moving the reference bank to its fully inserted position with all other banks fully withdrawn and recording the core reactivity and moderator temperature. From this point, a rod swap maneuver was performed by withdrawing the reference bank several steps and then inserting one of the other control rod banks_ (i.e .*. a_.test hank) _to _balance.the_ reactivity_ oLthe_reference. hank withdrawal.
This sequence was repeated until the test bank was fully inserted and the reference bank was positioned such that the core was just critical or near the initial statepoint condition.
This measured critical position (MCP) of the reference bank with the test bank fully NE-1206 S2C16 Startup Physics Tests Report Page 20 of 55
inserted was used to determine the integral reactivity worth of the test bank. The core reactivity, moderator temperature, and the differential worth of the reference bank were recorded with the reference bank at the MCP. The rod swap maneuver then was repeated in reverse such that the reference bank again was fully inserted with the test bank fully withdrawn from the core. This rod swap process was then repeated for each of the other control and shutdown banks.
A summary of the test results is given in Table 3.1. As shown in this table and the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the individual measured bank worths for the control and shutdown banks were within the design tolerance (+/-10% for the referern:::e bank, +/-15% for test banks of worth greater than 600 pcm, and +/-100 pcm for test banks of worth less than or equal to 600 pcm). The sum of the individual measured rod bank worths was within 1.1 % of the design prediction. This is well within the design tolerance of+/- 10% for the sum of the individual control rod bank worths.
The integral and differential reactivity worths of the reference bank (Control Bank B) are shown in Figures 3.1 and 3.2, respectively. The design predictions and the measured data are plotted together in order to illustrate their agreement. In summary, the measured rod-worth values were satisfactory.
NE-1206 S2C16 Startup Physics Tests Report Page 21 of 55
Table 3.1 SURRY UNIT 2- CYCLE 16 STARTUP PHYSICS TESTS CONTROL ROD BANK WORTH
SUMMARY
MEASURED PREDICTED PERCENT WORTH WORTH DIFFERENCE (%)
BANK (PCM) (PCM) (M-P)/P X 100 B-Reference Bank 1233 1263 -2.4 D 1044 1020 2.3 C 915 881 3.9 A 202 199 1.5*
SB 1233 1190 3.6 SA 903 916 -1.4 Total Worth 5530 - 5469 1.1
- Difference is less than 100 pcm.
NE-1206 S2C16 Startup Physics Tests Report Page 22 of 55
Figure 3.1 SURRY UNIT 2- CYCLE 16 STARTUP PHYSICS TESTS CONTROL BANK B INTEGRAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 140.0 1200 r-.
- ~ '\
\
\.
I\
- i::
....0 1000 I\
IQ \
....It, \
..... I\
au ~
P, 800 0 I\
N
\
- Measured
.s::
.1,1 k
'\
. --Predicted i \
-~
600 -l"C fd Ill '\
r-1 l\.o al k '\
tll CD
.1,1
...i:: 400 I'\.
' l:l.
200 '.
I,.
r.-.
~
0 0 40 80 120 160 200 Bank Position (5 steps/divisi~n)
NE-1206 S2C16 Startup Physics Tests Report* Page 23 of 55
Figure 3.2 SURRY UNIT 2-CYCLE 16 STARTUP PHYSICS TESTS CONTROL BANK B DIFFERENTIAL ROD WORTH - HZP ALL OTHER RODS WITHDRAWN 10 - ~* ***- -*- - ----~ - - -- *--* 1-T T--~ -- -- -- . . - -** *......-,--r--*
9
,~I"\.
I I\.
I\
I i. \
1* I\
8 I \
I It s:: / 14 0 \
Ill
"".....'ti 7
' I\ '-
I Cl, a, ,.I '
~
""Ill
..... 6 ~ ""'
au 1*
N Cl, I
I e
.s:::
5 .
, I\
II
- Measured
--Predicted
""... II i I
'ti 0 4 p:
ri Ill
""""s::
a, I I ...
...a, 3 1M 1M
""C I ,
2 J
I/
I/
I 0
0 40 80 120 160 200 Bank Position (5 steps/division)
NE-1206 S2C16 Startup Physics Tests Report Page 24 of 55
SECTION 4 BORON ENDPOINT AND WORTH MEASUREMENTS Boron Endpoint With the reactor critical at hot zero power, reactor coolant system (RCS) boron concentrations were measured at selected rod bank configurations to enable a direct comparison of measured boron endpoints with design predictions. For each critical boron concentration measurement, the RCS conditions were stabilized with the control banks at or very near a selected endpoint position. Adjustments to the measured critical boron concentration values were made to account for off-nominal control rod position- and moderator temperature, ifnecessary.
The results of these measurements are given in Table 4.1. As shown in this table and in the Startup Physics Test Results and Evaluation Sheets given in the Appendix, the measured critical boron endpoint values were within their respective design tolerances.
The all-rods-out (ARO) endpoint comparison to the predicted value met the requirements of Technical Specification 4.10.A regarding core reactivity balance. In summary, the boron endpoint results were satisfactory.
Boron Worth Coefficient The measured boron endpoint values provide stable statepoint data from which the boron worth coefficient or differential boron worth (DBW) was determined. By relating each endpoint concentration to the integrated rod worth present in the core at the NE-1206 S2Cl6 Startup Physics Tests Report Page 25 of 55
time of the endpoint measurement, the value of the DBW over the range of boron endpoint concentrations was obtained.
A summary of the measured and predicted DBW is shown in Table 4.2. As indicated in this table and in the Appendix, the measured DBW was wel~ within the design tolerance of +/-IQ%. In summary, the measured boron worth coefficient was satisfactory.
NE-1206 S2C16 Startup Physics Tests Report Page 26 of 55
Table 4.1 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS BORON ENDPOINTS
SUMMARY
Measµred Predicted Difference Control Rod Endpoint Endpoint M-P Configuration (ppm) (ppm) (ppm)
ARO 1889 1876 13 B Bank In 1726 1712* 14
- The predicted endpoint for the B Bank In configuration was adjusted for the difference between the measured and predicted values of the endpoint taken at the ARO configuration as shown in the boron endpoint Startup Physics Test Results and Evaluation Sheet in the Appendix.
NE-1206 S2C16 Startup Physics Tests Report Page 27 of 55
Table 4.2 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS BORON WORTH COEFFICIENT Measured Predicted Percent Boron Worth Boron Worth Difference (%)
(pcm/ppm) (pcm/ppm) (M-P)/P x 100
-7.56 -7.14 5.9 NE-1206 S2C16 Startup Physics Tests Report Page 28 of 55
SECTION 5 TEMPERATURE COEFFICIENT MEASUREMENT The isothermal temperature coefficient .(ITC) at the all-rods-out condition is measured by controlling tl!.e reactor .coolant system (RCS) temperature by varying the amount of steam generator blowdown flow to establish a constant heatup or cooldown rate, and monitoring the resulting reactivity changes on the reactivity computer.
Reactivity was .measured during the RCS cooldown of 2.9°F and RCS heatup of 3.3°F. Reactivity and temperature data were taken from the reactivity computer and strip chart recorders. Using the statepoint method, the temperature coefficient was determined by dividing the change in reactivity by the change in RCS temperature. An X-Y plotter, which plotted reactivity versus temperature, confirmed the statepoint method in calculating the measured ITC.
The predicted and measured isothermal temperature coefficient values are compared in Table 5.1. As can be seen from this summary and from the Startup Physics Test Results and Evaluation Sheet given in the Appendix, the measured isothermal temperature coefficient value was within the design tolerance of +/-3 pcml°F. The moderator temperature coefficient was determined to be 0.65 pcml°F which met the requirements of COLR Section 2.1.1. In summary, the measured results wer_e satisfactory.
NE-1206 S2C16 Startup Physics Tests Report Page 29 of 55
Table 5.1
- -SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS ISOTHERMAL TEMPERATURE COEFFICIENT
SUMMARY
ISOTHERMAL TEMPERATURE BANK TEMPERATURE BORON COEFFICIENT (PCM/°F)
POSITION RANGE CONCENTRATION AVE DIFFER (STEPS) (OF) (ppm) CID H/U MEAS PRED (M-P) 544.4 D/212 to 1885 -1.2 -0.9 -1.05 -2.74 1.69 548.5 NE-1206 S2C16 Startup Physics Tests Report Page 30 of 55
SECTION 6 POWER DISTRIBUTION MEASUREMENTS The core power distributions were measured using the moveable incore detector flux mapping system. This system consists of five fission chamber detectors which traverse fuel assembly instrumentation thimbles in up to 50 core locations. Figure 1.3 shows the available locations monitored by the moveable detectors for the ramp to full power flux maps for Cycle 16. For each traverse, the detector' voltage output is continuously monitored.on a strip chart recorder, and scanned for 61 discrete axial points by the PRODAC P-250 process computer. Full core, three-dimensional power.
distributions are determined from this data using a Virginia Power modified version of the Combustion Engineering computer program, CECOR3 . CECOR couples the measured voltages with predetermined analytic power-to-flux ratios in order to determine the power distribution for the whole core.
A list of the full-core flux maps taken during the startup test program and the measured values of the important power distribution parameters are given in Table 6.1. A comparison of these measured values with their COLR8,4 limits is given in Table 6.2.
Flux map 1 was taken at 22.9% power to verify the radial power distribution (RPD) predictions. at low power. . Figure 6.1 shows the measured RPDs from this flux map. Flux
/
maps 2 and 3 were taken at 65.3% and 100% power, respectively, with different control rod configurations. These flux maps were taken to check at-power design predictions and NE-1206 S2C16 Startup Physics_Tests Report Page 31 of 55<
to measure core power distributions at various operating conditions. The radial power distributions for these maps are given in Figures 6.2 and 6.3. The radial power distributions for the maps given in Figures 6.1, 6.2, and 6.3 show that the averaged measured relative assembly* power values were generally within 2.2 % of the predicted values. Further, the measured F-Q(Z) and F-DH(N) peaking factor values for the at-power flux maps were within the limits of COLR Sections 2.3 and 2.4, respectively. Flux maps 1 and 2 were also used to perform power range detector calibrations. The flux map analyses are documented in Reference 7.
In conclusion, the power distribution measurement results were considered to be acceptable with respect to the design tolerances, the accident analysis acceptance criteria, and the COLR. It is therefore anticipated that the core will continue to operate safely throughout Cycle 16.
NE-1206 S2C16 Startup Physics Tests Report Page 32 of 55
Table 6.1 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS INCORE FLUX MAP
SUMMARY
Bum Bank Peak F-Q(Z) Hot(l) F-DH(N) Hot Core F(Z) (2) Axial No.
Map Map up Pwr D Channel Factor Channel Factor Max Core Tilt off of Description No. Date MWD/ % Steps Assy Axial F-Q(Z) Assy F-DH(N) Axial F(Z) Max Loe set Thim MTU Point point (%) bles
~wPower 1 5/30/99 5 23 162 JlO 26 2.202 110 1.526 30 1.316 1.0201 SE 2.142 41 Int. Pwr (3) 2 5/31/99 26 65 189 JlO 24 1.960 110 1.494 26 1.196 1.0126 SE 1.648 44 Hot Full Pwr 3 6/18/99 604 100 226 JlO 24 1.837 110 1.490 30 1.143 1.0102 SE 0.237 44 NOTES: Hot spot locations are specified by giving assembly locations (E.G. H-8 is the center-of-core assembly) and core height (in the "Z" direction the core is divided into 61 axial points
- starting from the top of the core).
(I) F-Q(Z) includes a total uncertainty of 1.08.
(2) CORE TILT - defined as the average quadrant power tilt from CECOR.
(3) Int. Pwr - intermediate power flux map.
(4) MAPS I, 2, and 3 were used for power range detector calibrations.
NE-1206 S2C16 Startup Physics Tests Report Page 33 of 55
Table 6.2 SURRY UNIT 2- CYCLE 16 STARTUP PHYSICS TESTS COMPARISION OF MEASURED POWER DISTRIBUTION PARAMETERS WITH THEIR CORE OPERATING LIMITS Peak F-Q(Z) Hot F-Q(Z) Hot F-DH(N) Hot Map Channel Factor* Channel Factor** Channel Factor ,
(At Node of Minimum Margin)
No. Meas. Limit Node Meas. Limit Node Margin Meas. Limit Margin
(%) (%)
1 2.202 4.582 26 2.202 4.582 26 51.9 1.526 1.921 20.6 2 1.960 3.482 24 1.960 3.482 23 43.7 1.494 1.722 13.2 3 1.837 2.274 24 1.837 2.274 23 19.2 1.490 1.560 4.5
- The Core Operating Limit for the heat flux hot channel factor, F-Q(Z), is a function of core height and power level. The value for F-Q(Z) listed above is the maximum value of F-Q(Z) in the core. The COLR limit listed above is evaluated at the plane of maximum F-Q(Z).
- The value for F-Q(Z) listed above is the value at the plane of minimum margin, The minimum margin values listed above are the minimum percent difference between the measured values of F-Q(Z) and the COLR limit for each map.
The measured F-Q(Z) hot channel factors include 8% total uncertainty.
NE-1206 S2C16 Startup Physics Tests Report Page 34 of 55
Figure 6.1 SURRY UNIT 2-CYCLE 16 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 23%POWER p N .. M L K J H G F E D C B A PREDICTED *
- 0.205
- 0.220
- 0.206. PREDJ:CTED MEASURED
- 0.199
- 0.213
- 0.201. MEASURED 1
- 0.280
- 0.459
- 0.998
- 0.636
- 1.001. 0.462
- 0.282 *
- 0.267
- 0.444
- 0.973
- 0.617
- 0.976
- 0.456
- 0.278
- 2
-4.9 * -3.4 * -2.5 * -2.9 * -2.6 * -1.1 * -1.6 *
- 0.323
- 1.081
- 1.266
- 1.212
- 1.296
- 1.216
- 1.272
- 1.091
- 0.327 *
- 0.312 .-1.024
- 1.219
- 1.190
- 1.240
- 1.181. 1.243
- 1.072
- 0.329 .* 3
-3.6 * -5.3 * -3.7 * -1.8 * -4.3 * -2.9 * -2.3 * -1.7
- 0.5 *
- 0.326
- 0.663 , 1.301
- 1.256
- 1.344
- 1.347
- 1.347
- 1.261
- 1.311
- 0.665
- 0.324 *
- 0.310
- 0.626
- 1.203
- 1.203
- 1.308
- 1.310
- 1.316
- 1.227
- 1.288
- 0.655
- 0.320
- 4
-4.9 . -5.7 * -7.5 * -4.2 . -2.6 * -2.7 * -2.3 * -2.7 * -1.8 * -1.6 * -1.4 *
- 0.279
- 1.088
- 1.306
- 1.229
- 1.304
- 1.264
- 1.342
- 1.264
- 1.306
- 1.231
- 1.303
- 1.085
- 0.280 *
- 0.267
- 1.042
- 1.248
- 1.169
- 1.265
- 1.244
- 1.328
- 1.257
- 1.298
- 1.220
- 1.277
- 1.073
- 0.275
- 5
-4.2 * -4.2 * -4.4 . -4.9 * -3.0 * -1.6 * -1.1. -0.6 * -0.6 * -0.9 * -2.0 * -1.1 * -1.7 *
- 0.461. 1.268
- 1.257
- 1.305
- 1.167
- 1.325
- 1.255
- 1.322. 1.166
- 1.303
- 1.256
- 1.267
- 0.460 *
- 0.443
- 1~218
- 1.213
- 1.269
- 1.155
- 1.329
- 1.268. 1.342. 1.192
- 1.312
- 1.254
- 1.267
- 0.461
- 6
-3.9 * -3.9 * -3.5 * -2.8 * -1.1
- 0.3
- 1.0. 1.5. 2.2
- 0.7 * -0;1
- 0.0
- 0.3 a
- 0.205
- 0.998
- 1.209
- 1.342
- 1.263
- 1.324
- 1.256
- 1.273
- 1.253
- 1.321
- 1.262
- 1.343
- 1.209
- 0.997
- 0.205 *
- o.198
- o.963
- 1.159
- 1.306
- 1.244
- 1.328
- 1.291
- 1.304
- 1.293
- 1.354
- 1.203
- 1.354
- 1.221. r;oo9
- 0.200
- 7
-3.4 * -3.5 * -4.2 * -2~7 * -1.5
- 0.3
- 2.7
- 2.4
- 3.2
- 2.5 *. 1.6
- 0.8
- 1.0 **,:_;:-1.2
- 1.4 * .., *-~~
- 0.220
- 0.635
- 1.291
- 1.343
- 1.340
- 1.252
- 1.269
- 1.238
- 1.269
- 1.252
- 1.340
- 1.343
- 1.291
- 0.635
- 0.220 *
- 0.215
- 0.621
- 1.275
- 1.321
- 1.326
- 1.264
- 1.302
- 1.271. 1.305. 1.289
- 1.371
- 1.370
- 1.315
- 0.649 . 0.225
- 8
- , -2.5 * -2.1 * -1.*3 * -1.6 * -1.0
- 0.9
- 2.6
- 2.7
- 2.8
- 2.9
- 2.3
- 2.0
- 1.8 * ~-3
- 2.2 *
- 0.205
- 0.997
- 1.209
- 1.343
- 1.262
- 1.321. 1.253
- 1.273
- 1.256
- 1.324
- 1.263
- 1.342 *. l.209
- 0.998
- 0.205 * . :; .
- 0.199
- 0.971
- 1.180
- 1.323
- 1.262
- 1.347
- 1.301
- 1.314
- 1.286
- 1.367
- 1.299
- 1.382
- 1.239
- 1.018
- 0.210
- 9
-2.6 * -2.5 * -2.4 . -1.4 * -0.l
- 2.0
- 3.9
- 3.2
- 2.3
- 3.2
- 2.8
- 2.9
- 2.5
- 2.0
- 2.1 *
- 0.460
- 1.267
- 1.256
- 1.303
- 1.166
- 1.322
- 1.255
- 1.325. 1.167
- 1.305
- 1.257
- 1.268
- 0.461 *
- 0.443
- 1.210
- 1.236
- 1.311
- 1.203
- 1.424
- 1.304
- 1.357
- 1.191
- 1.342
- 1.315
- 1.306
- 0.461, 10
-3.6 * -4.5 * -1.5
- o.6
- 3.2
- 1.1
- 3.9
- 2.4
- 2.1 * *2.0
- 4.6
- 3.o
- 0.1 *
- o.2ao
- 1.005
- 1.303
- 1.231
- 1.306
- 1.264
- 1.342
- 1.264
- 1.304
- 1.229
- 1.306
- 1.000
- 0.219 *
- 0.212
- 1.057
- 1.292
- 1.244
- 1.330
- 1.299
- 1.371. 1.201. 1.298
- 1.251
- 1.345 .-1.119
- 0;285
- 11
-3.0 * -2.6 * -0.8
- 1.1
- 1.9
- 2.7
- 2.1. 1.3 * -0,5
- 1.8
- 2.9
- 2.9
- 1.9
- 0.324 0.665 1.311 1.261 1.347
- 1.347 1.344 1.256 1.301 0.663 0.326
- 0.319
- 0.664
- 1.320
- 1.269
- 1.337
- 1.367
- 1.359
- 1.261
- 1.315
- 0.677
- 0.335
- 12
-1.6 * -0.2
- 0.1
- 0.1 * -0.0
- 1.5
- 1.1
- o.4
- 1.1
- 2.1
- 2.0
- 0.327 1.091 1.272 1.216 1.296 1.212 1.266 1.081 0.323
- 0.328
- 1.099
- 1.285
- 1.232
- 1.340
- 1.231. 1.265
- 1.087
- 0.327
- 13 0.3
- 0.8
- 0.9
- 1.3
- 3.4
- 1.5 * -0.1
- 0.6
- 1.1 *
- * *
- a; * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *
- 0.282 0.462
- 1.001
- 0.636
- 0.998. 0.459
- 0.280 *
- 0.286
- 0.467
- 1.019
- 0.653
- 1.015
- 0.462
- 0.282
- 14 1.2.. 1.2
- 1.7
- 2.6
- 1.7
- 0.6 . 0.5
- STANDARD 0.206 0.220 0.205 AVERAGE DEVJ:ATJ:ON *
- 0.210
- 0.225
- 0.208 * .PCT DJ:FFERENCE. 15
=1.368 1.7
- 2.2
- 1.7 *
- 2.2
SUMMARY
Map No.: S2-16-01 Date: 05/30/99 Power: 22.86%
Control Rod Positions: F-Q(Z) = 2.202 QPTR:
D Bank at 162 steps F-DH(N) = 1.526 NW 0.97451 NE 0.9990 F(Z) = 1.316 SW 1.0065 I SE 1.0201 Burnup = 4.5 MWD/MTU A. 0. = 2.142%
NE-1206 S2C16 Startup Physics Tests Report Page 35 of 55
Figure 6.2 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 65%POWER R p N -M L K J H G F E D C B A PREDICTED
- 0.223
- 0.245
- 0.225
- PREDICTED MEASURED
- 0.220
- 0.241
- 0.221
- MEASURED 1
.PCT DIFFERENCE. -1.3 * -1.6 * -1.6 * .PCT DIFFERENCE.
- 0.290
- 0.474
- 1.027
- 0.692
- 1.030
- 0.476
- 0.292 *
- 0.279
- 0.464 . 1.014
- 0.680
- 1.014
- 0.470
- 0.289
- 2
-3.6 * -2.2 * -1.2 * -1.7 * -1.5 * -1.2 * -1.0 *
- 0.332
- 1.067
- 1.242
- 1.205
- 1.287
- 1.208
- 1.247
- 1.075
- 0.336 *
- 0.326
- 1.023
- 1.211
- 1.198
- 1.257
- 1.189
- 1.232
- 1.067
- 0.340
- 3
-2.0 * -4.1 * -2.5 * -0.6 * -2.4 * -1.6 * -1.2 * -0.7
- 1.4 *
- - 0.335
- 0.667
- 1.269
- 1.232
- 1.313
- 1.320
- 1.316
- 1.235
- 1.277
- 0.669
- 0.333 *
- 0.323
- 0.639
- 1.186
- 1.194
- 1.292
- 1.293
- 1.300
- 1.220
- 1.265
- 0.661
- 0.329
- 4
-3.5 * -4.3 * -6.6 * -3.0 * -1.6 * -2.0 * -1.2 * -1.3 * -0.9 * -1.2 * -1.2 *
- 0.289
- 1.074
- 1.274
- 1.214
- 1.295
- 1.257
- 1.321. 1.257
- 1.296
- 1.215
- 1.270
- 1.071
- 0.290 *
- 0.281. 1.044
- 1.238
- 1.184
- 1.274
- 1.250
- 1.319
- 1.259
- 1.294
- 1.207
- 1.246
- 1.059
- 0.286
- 5
-2.8 * -2.8 * -2.8 * ~2.5 * -1.6 * -0.5 * -0.2
- 0.2 * -0.1 * -o.6 * -1.9 * -1.1 * -1.4 *
- 0.476. 1.244
- 1.233
- 1.296
- 1.229 ** 1.340
- 1.260
- 1.337
- 1.227
- 1.295
- 1.232 1.243 0.475 *
- 0.462
- 1.211. 1.205
- 1.273
- 1.224
- 1.354
- 1~285
- 1.364
- 1.244
- 1.299
- 1.227
- 1.239
- 0.474 . 6
-2.7 * -2.~ * . -2.3 * -1.8 * -0.4
- 1.1
- 2.0
- 2.0
- 1.4 . 0.4 . -0.3 * -0.4 * -0.1 *
- 0.224
- 1.027 1.203 1.312 1.257 1.339 1.271 1.282 1.267 1.336. 1.256. 1.313. 1.203 1.027. 0.224
- 0.218
- 1.000
- 1.167
- 1.286
- 1.243
- 1.348
- 1.310
- 1.322
- 1.323
- 1.367
- 1.271
- 1.318
- 1.206
- 1.032
- 0.225
- 7
-2.7 * -2.6 * -3.0 * -2.0 * -1.1
- 0.7
- 3.1
- 3.1
- 4.4 . 2.3
- 1.2
- 0;4 . 0.3 * - 0.6
- 0.4 .
- 0.246
- 0.691
- 1.284
- 1.317
- 1.319
- 1.257
- 1.278
- 1.241
- 1.278
- 1.257
- 1.319
- 1.317
- 1.284
- 0.691. 0.246 *
- 0.240
- 0.676
- 1.262
- 1.298
- 1.303
- 1.269
- 1.311
- 1.277
- 1.317
- 1.282
- 1.340
- 1.332
- 1.289
- 0.686
- 0.245
- 8
-2.4 * -2.2 * -1.7 * -1.5 * -1.2
- 1.0
- 2.5
- 2.9
- 3.0
- 2.0
- 1.6
- 1.1
- 0.4 * -0.7 * -0.2 *
- 0.224
- 1.027
- 1.203
- 1.313
- 1.256
- 1.336
- 1.267
- 1.282
- 1.271
- 1.339
- 1.257
- 1.312
- 1.203
- 1.027
- 0.224 *
- 0.218
- 0.999
- 1.173
- 1.297
- 1.268
- 1.361
- 1.307
- 1.320
- 1.306
- 1.375
- 1.283
- 1.338
- 1.220
- 1.036
- 0.225
- 9
-2.7 * -2.7 * -2.5 * -1.2
- 1.0
- 1.8
- 3.1
- 3.0
- 2.7
- 2.7
- 2.1
- 2.0
- 1.4
- 0.9
- 0.1 *
- 0.475
- 1.243
- 1.232
- 1.295
- 1.227
- 1.337
- 1.260
- 1.340
- 1.229 . 1.296
- 1.233
- 1.244
- 0.476 *
- 0.457
- 1.183
- 1.212
- 1.301
- 1.253
- 1.405
- 1.300
- 1.369
- 1.250
- 1.324
- 1.276
- 1.272
- 0.485
- 10
-3.8 * -4.8 . -1.6
- 0.5
- 2.1
- 5.1
- 3.2
- 2.2
- 1.7
- 2.1
- 3.5
- 2.2
- 1.9 *
- 0.290
- 1.071. 1.270
- 1.215
- 1.296
- 1.257
- 1.321
- 1.257
- 1.295
- 1.214
- 1.274 1.074
- 0.289 *
- 0.281
- 1.041
- 1.256.* 1.222
- 1.311
- 1.282
- 1.351
- 1.272
- 1.292 .* 1.230
- 1.300
- 1.094
- 0.294
- 11
-3.2 * -2.8 * -1.1
- 0.6
- 1.2
- 2.0
- 2.3
- 1.2 * -0.2
- 1.3
- 2.0
- 1.9
- 1.8 *
- 0.333
- 0.669
- 1.277
- 1.235
- 1.316
- 1.320
- 1.313
- 1.232
- 1.269
- 0.667 0.335 *
- 0.328
- 0.665
- 1.279
- 1.238
- 1.304
- 1.333
- 1.320
- 1.228
- 1.272
- 0.673
- 0.334
- 12
-1.5 * -0.6
- 0.2
- 0.2 * -0.9
- 1.0
- 0.5 * -0.3
- 0.2
- 0.9 * -0.2
- 0.336
- 1.075
- 1.247
- 1.208
- 1.287
- 1.205
- 1.242
- 1.067
- 0.332
- 0.335
- 1.076
- 1.250
- 1.214
- 1.313
- 1.208
- 1.218
- 1.059
- 0.331. 13
-0.2
- 0.1
- 0.3
- 0.5
- 2.0
- 0.3 * -1.9 * -0.7 * -0.2
- 0.292 0.476 1.030 0.692 1.027 0.474 0.290
, 0.290
- 0.477
- 1.035
- 0.700
- 1.030
- 0.469
- 0.288
- 14
-0.8
- 0.2
- 0.5
- 1.1
- 0.3 * -0.9 * -0.9
- STANDARD 0.225 0.245 0.223 AVERAGE DEVIATION *
- 0.221
- 0.246
- 0.224 * .PCT DIFFERENCE. 15
=1.153 -1.7
- 0.3
- 0.3 *
- 1.6
SUMMARY
Map No.: S2-l-6-02 -Date: 05/31/99 -* Power: 65.3%
Control Rod Positions: F-Q(Z) = 1.960 QPTR:
D Bank at 189 steps F-DH(N) = 1.494 NW 0.98441 NE 1.0013 F(Z) = 1.196 SW 1.0017 I SE 1.0126 Burnup = 26.2 MWD/MTU A. 0. = 1.648%
NE-1206 S2C16 Startup Physics Tests Report Page 36 of 55
Figure 6.3 SURRY UNIT 2 - CYCLE 16 STARTUP PHYSICS TESTS ASSEMBLYWISE POWER DISTRIBUTION 100% POWER R p N .M L K J H G F E D C B A PREDICTED
- 0.237
- 0.265
- 0.238
- PREDICTED MEASURED
- 0.235
- 0.261
- 0.235
- MEASURED 1
- 0.301
- 0.485
- 1.038
- 0.742
- 1.040
- 0.487
- 0.302 *
- 0.293
- 0.480
- 1.034
- 0.731
- 1.029
- 0.487
- 0.302
- 2
-2.5 * -l.l * -0.3 * -1.5 * -1.1
- 0.1 * -0.2 .
0.344
- 1.063 1.234 1.196 l.286 1.199 1.238 1.070 0.348
- 0.343
- 1.030
- 1.216
- 1.204
- 1.251
- 1.182
- 1.226
- 1.066
- 0.360
- 3
-0.3 * -3.1 * -1.4
- 0.7 * -2.7 * -1.4 * -0.9 * -0.4
- 3.4 *
- 0.347 0.679 1.263 1.219 1.300 l.298 1.302 1.222 1.271 0.680 0.345
- 0.337
- 0.655
- 1.190
- 1.193
- 1.292
- 1.286
- 1.291
- 1.206
- 1.258 . 0.671
- 0.339
- 4
-2.9 * -3.5 * -5.8 * -2.1 * -0.6 . -0.9 * -0.9 * -1.4 * -1.0 * -1.4 * -1.7
- 0.297 1.067 1.268 1.211 1.302 l.246 1.305 1.246 1.303 1.212 1.264 1.064 0.298
- 0.290
- 1.042
- 1.241
- 1.199
- 1.292
- 1.249
- 1.313
- l.251
- 1.300
- 1.200
- 1.226
- 1.045 . 0.293
- 5
-2.5 * -2.4 * -2.1 * -1.0 * -0.8
- 0.3
- 0.6
- 0.4 * -0.2 ; -1.0 * -3.0 * -1.8 * -1.7 *
- 0.486
- 1.235 1.220
- 1.303
- 1.281 1.331
- 1.241 1.329 1.280 1.301
- 1.219
- 1.233 0.485
- 0.473
- 1.203
- 1.193
- 1.273
- 1.280
- 1.353
- 1.274
- 1.357
- 1.295
- 1.303
- 1.209
- l.223
- 0.482
- 6
-2.7 * -2.6 * -2.2 * -2.3 * -0.1
- 1.7
- 2.7
- 2.1
- 1.2
- 0.1 * -0.8 * -0.8 . -0.5 *
- 0.237
- 1.038
- 1.193
- 1.299
- 1.246
- 1.330
- 1.254
- 1.257
- 1.251
- 1.328
- 1.245
- 1.299
- 1.193
- 1.037 -* 0.237 *
- 0.231
- 1.010
- 1.156
- 1.272
- 1.230
- 1.342
- 1.300
- l.301
- 1.302
- 1.358
- 1.258
- 1.303
- 1.192
- 1.040
- 0.237
- 7
-2.7 * -2.7 * -3.l * -2.l * -1.3
- 0.9
- 3.7
- 3.4
- 4.1
- 2.2
- 1.1
- 0.3 . -0.l
- 0.3
- 0.2 *
- 0.265
- 0.741
- l.283
- 1.295
- 1.304
- 1.239
- 1.254
- 1.224
- l.254
- 1.239
- 1.304
- 1.295
- 1.283
- 0.741
- 0.265 *
- 0.259
- 0.725
- l.266
- l.275
- l.283
- 1.251
- 1.290
- 1.262
- 1.294
- 1.270
- 1.325
- 1.306
- 1.279
- 0.736
- 0.266
- 8
-2.3 * -2.2 * -1.4 * -1.6 * -1.6
- 1.0
- 2.9
- 3.1
- 3.2
- 2.5
- 1.6
- 0.8 * -0.3 * -0.6
- 0.1 *
- 0.237
- 1.037
- 1.193
- 1.299
- 1.245
- 1.328
- 1.251 . 1.257
- 1.254
- 1.330
- 1.246
- 1.299
- 1.193
- 1.038
- 0.237 *
- 0.231
- 1.010
- 1.164
- 1.282
- 1.254
- 1.353
- 1.294
- 1.297
- 1.290
- 1.375
- 1.272
- 1.320
- 1.206
- 1.046
- 0.243
- 9
- *-2.6 * -2.6 * -2.4 . -1.3
- 0.7
- 1.9
- 3.5
- 3.2
- 2.9
- 3.4
- 2.1
- 1.6
- l.O
- 0.9
- 2.2 *
- 0.485
- 1.233
- 1.219
- 1.301
- 1.280
- 1.329
- 1.241
- 1.331
- 1.281
- 1.303
- 1.220
- l.235
- 0.486 *
- 0.467
- 1.175
- 1.197
- 1.304
- 1.309
- 1.408 . 1.279
- 1.358
- 1.302
- 1.325
- 1.253
- l.258
- 0.494
- 10
-3.7 * -4.7 * -1.8
- 0.2
- 2.2
- 6.0 . 3.1
- 2.0
- 1.6
- 1.7
- 2.7
- 1.9
- 1.7 *
- 0.298
- 1.064
- 1.264
- 1.212
- 1.303
- 1.246
- 1.305
- 1.246
- 1.302
- 1.211
- 1.268
- 1.067
- 0.297 *
- 0.289
- 1.033
- 1.245
- 1.208 . 1.312
- 1.265 . 1.318
- 1.252
- 1.290
- 1.218
- 1.290
- 1.089
- 0.303
- 11
-3.2 * -2.9 * -1.5 * -0.3 . 0.7
- l.5
- 0.9
- 0.5 * -0.9
- 0.6
- l.7
- 2.0
- 1.9 *
- 0.345
- 0.680
- 1.271
- 1.222
- 1.302 . 1.298
- 1.300
- 1.219
- 1.263
- 0.679
- 0.347 *
- 0.339
- 0.673
- 1.265
- 1.217
- 1.278
- 1.299
- 1.298
- 1.210
- 1.263
- 0.690
- 0.358
- 12
-1.6 * -1.0 * -0.5 * -0.4 . -1.8 . 0.1 * -0.2 * -0.8
- 0.0
- 1.7
- 3.2
- 0.348 . 1.070
- 1.238 1.199
- 1.286
- 1.196
- 1.234
- 1.063
- 0.344 .
- 0.346
- 1.067
- 1.234
- 1.197 . 1.303
- 1.193
- 1.207
- 1.053
- 0.345
- 13
-0.6 * -0.3 * -0.3 . -0.2
- 1.3 * -0.3 * -2.2 * -0.9
- 0.0 *
- 0.302 0.487 1.040
- 0.742
- 1.038
- 0.485
- 0.301 *
- 0.303
- 0.486
- 1.042
- 0.745
- 1.036
- 0.479 -* 0.297
- 14 0.2 . -0.1
- 0.2
- 0.4 * -0.2 . -1.3 * -1.1
- STANDARD 0.238
- 0.265 0.237 AVERAGE DEVIATION
- 0.239
- 0.265
- 0.236 * .PCT DIFFERENCE. 15
=1.177 0.3
- 0.3 * -0.2
- 1.5
SUMMARY
Map No.: S2-16-03 Date: 06/18/99 Power: 99.97%
Control Rod Positions: F-Q(Z) = 1.837 QPTR:
D Bank at 226 steps F-DH(N) = 1.490 NW 0.9893 I NE 1.0010 I
F(Z) = 1.143 SW 0.9995 I SE 1.0102 Burnup = 604MWD/MTU A. 0. = 0.237%
NE-1206 S2C16 Startup Physics Tests Report Page 37 of 55
SECTION?
REFERENCES
- 1. M.A. Hofmann, "Surry Unit 2, Cycle 16 Design Report", Technical Report NE-1197, Revision 0, Virginia Power, May, 1999.
- 2. T. K. Ross, W. C. Beck, "Control Rod Reactivity Worth Determination By The Rod Swap Technique," VEP-FRD-36A, December, 1980.
- 3. T. W. Schleicher, "The Virginia Power CECOR Code Package", Technical Report NE-831, Revision 4, Virginia Power, August, 1998.
- 4. Surry Unit 1 and 2 Technical Specifications, Sections 3.1.E.1, 3.12.B.1, 3.12.C.1, 4.10.A, and 5.3.A.6.b.
- 5. Letter from W. L. Stewart (Virginia Power) to the U.S.N.R.C, "Surry Power Station Units 1 and 2, North Anna Power Station Units 1 and 2: Modification of Startup Physics Test Program - Inspector Followup Item 280, 281/88-29-01 ", Serial No.89-541, December 8, 1989.
- 6. C. D. Clemens, "Surry 2, Cycle 16 TOTE Calculations", PM-800, Revision 0, May, 1999.
- 7. R. A. Hall, et al, "Surry 2, Cycle 16 Flux Map Analysis", PM-804, Revision 0, and Addenda A and B, May- June, 1999.
- 8. S.S. Kere, "Reload Safety Evaluation, Surry 2 Cycle 16 Pattern AG", Technical Report NE-1190, Revision 2, May, 1999.
NE-1206 S2C16 Startup Physics Tests Report Page 38 of 55
APPENDIX STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEETS NE-1206 S2C16 Startup Physics Tests Report Page 39 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Zero Power Testing Range Determination Reference Proc No/ Section: 2-NPT-RX-008
- Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Desiqn) CB: 226 CC:
- CD:
- Below Nuclear Heatino 111 Bank Positions (Steps) RCS Temperature (°F): S%,~
Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: 226 CC: 22..Cii CD: 97 Below Nuclear Heating Date/Time Test Performed:
~lls/ci9 !31D Reactivity Computer Initial
-9 Flux Background Reading l.27~7'f./O amps IV Test Results Flux Reading At _,.,
Point Of Nuclear Heating 2 ,fb'{.t 0 amps
-i -~
Zero Power Testing Range I Y..10 to /0 'I-IO amps Reference Not Applicable V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met** V YES - - NO Acceptance Criteria is met**: V YES NO VI
- At The Just Critical Position Comments ** Design Tolerance and Acceptance Criteria are met if ZPTR is belo'trthe Po1nt bfNuclea/Hea:ting and above *background.
Prepared By: ru~ f ~ Reviewed By:
NE-1206 S2Cl6 Startup Physics Tests Report Page 40 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test"Description: Reactivity Computer Checkout Reference Proc No I Section: 2-NPT-RX-008 Seauence Steo No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB: 226 CC:
- CD:
- Below Nuclear Heatina Ill Bank Positions (Steps) RCS Temperature (°F): Sc.J.7,B Test Power l.,.evel (% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: 226 CC: ?_?_l. CD: '7 '2:> Below Nuclear Heating Date/Time Test Performed: 15!>0
...-~-2S-C,9 I I I ' * -
(I~
rrw.l S'*ZS.sri Measured Parameter Pc= Measured Heact1v1ty using p-computer (Description) Pt= Predicted Reactivity IV Test Results Measured Value Pc= -'5'0 .~ I ..le L\1. O Pt= - S l, ~ 1 -t l\7,t(o
%0= -3,.s I - /. (p Design Value %0= {(pc - Pt)lpt} X 100% ~ 4.0 %
Reference WCAP 7905, Rev. 1, Table 3.6 V FSAR/T ech Spec Not Applicable Acceptance Criteria Reference Not Applicable V YES Design Tolerance is met _ - - NO Acceptance Criteria is met : v7°YES NO VI
- At The Just Critical Position Comments The allowable range will be set based on the above results, as well as
-- --*results*from1he**benchmark*test.
Allowable Ranae = - Sb, 0 -to-+ 47.0 ~~
Prepared By: rvke.f~ Reviewed By:
NE-1206 S2C16 Startup Physics Tests Report Page 41 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Boron Concentration - ARO Reference Proc No/ Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (uF): 547 Test Power Level (% F.P .): O Conditions SDA: 226 SDB: 226. CA: 226 Other (specify):
(Design) CB: 226 CC: 226 CD: 226 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (uF): 5Y7.2 Test Power Level (% F.P .): 0 Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: 226 CC: 226 CD: 226 Below Nuclear Heating
- Date/Time Test Performed: AJ..o ~Jz.~/:;'t
- 5/z_t/"i.c, f~ .' GQ/(.,: ,y:i Measured Parameter (Cs)MAAO; Critical Boron Concentration - ARO (Description)
IV Test Results Measured Value (Cs)M ARo= J gii ppm (Design Conditions)
Design Value Cs= 1876 +/- 50 ppm (Design Conditions)
Reference Technical Report NE-1197, Rev. 0 0
V FSAR/Te.ch Spec laCs x Cs 1 ::::; 1000 pcm Acceptance Criteria Reference Technical Specification 4.10.A
'-- YES Design Tolerance is met - - NO Acceptance Criteria is met : ~YES NO VI Comments *aCe: * :..7.e9 pcm/ppm
- Ca°= l(Cs)MARo- Csl; Cs is design value Prepared By: Reviewed By:_~-~--~----
NE-1206 S2C16 Startup Physics Tests Report Page 42 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Isothermal Temperature Coefficient - ARO Reference Proc No/ Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (uF): 547 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB:
- 226 CC: 226 CD: 226 Below Nuclear Heating 111 Bank Positions (Steps) RCS Temperature (UF): S'fl. '-f Test Power Level (% F.P .): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: 226 CC: 226 CD: 212 Below Nuclear Heating
- Date/Time Test Performed:
- h.~1~'1 / 7
- f'1 Measured Parameter ( ISO) . Isothermal Temperature
.UT ARO*
(Description) Coefficient - ARO IV Test Measured Value (UTISO) ARO= -1.0,;- pcmf'F Results (Ca= /8-"is'~ ppm)
- Design Value (Actual Conditions) (a/SO)ARO= -7_,Jl/ +/-3.Q pcmf'F (Ca= i f'ir~ ppm)
Design Value (Design Conditions) (aT ISO )ARo= -2.82 +/-3.0 pcmf'F (C 8 = 1876 ppm)
Reference Technical Report NE-1197, Rev, O V FSAR/COLR ar1so ~ 3.80
- pcm/ °F Acceptance aTooP = -1.70 pcmfF Criteria Reference COLA 2.1.1,Technical Report NE-1197, Rev. O Design Tolerance is met ~ YES - - NO
..... Acceptance Criteria is met : YES NO VI Comments *Uncertainty on aTMoo =1L5 pcmfF ..(
Reference:
memorandum from C.T. Snow to E.J. Lozito dated June 27, 1980.)
Prepared By: Reviewed By:(jl)Afj,__ (p ~
NE-1206 S2C16 Startup Physics Tests Report Page 43 of 55 .
- SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Control Bank B Worth Measurement, Rod Swap Ref. Bank Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level (% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB: moving CC: 226 CD: 226 Below Nuclear Heatin~
Ill Bank Positions (Steps) RCS Temperature (UF): 5Y~.~
Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: *moving CC: 226 CD: 226 . Below Nuclear Heating
.. .::.Date7ime Test Performed:
5 lS /t;"> 7..G: I'-/
I Measured Parameter I REF.
Integral Worth Of Control Bank 8, 8 '
(Description) All Other Rods Out IV Measured Value I REF_
pcm Test 8 - 12..3.3.
Results Design Value (Design Conditions) 18REF= 1263 +/- 126 pcm Reference Technical Report NE-1197, Rev. O And Engineering Transmittal NAF 99-0047, Rev. O If Design Tolerance is exceeded, SNSOC shall V FSAR/Tech Spec evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-36A
~
~ YES Design Tolerance is met
~ YES
- - NO Acceptance Criteria is met : NO VI Comments Prepared By: ---+-"a""""M~--=-1-=J/J~- Reviewed By:<<~
NE-1206 S2C16 Startup Physics Tests Report Page44 of55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Critical Boron Concentration - B Bank In Reference Proc No/ Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA:. 226 Other (specify):
(DesiQn) CB: 0 CC: 226 CD: 226 Below Nuclear HeatinQ 111 Bank Positions (Steps) RCS Temperature (°F): S"l/7 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: 0 CC: 226 CD: 226 Below Nuclear Heating
- DateffimJ. Test Performed:
£" j?f .ff ").JOO Measured Parameter (Cste: Critical Boron Concentration, (Description) B Bank In _,
IV Test Results Measured Value (Cete= J 7J6 ppm (Design Conditions)
~.,
Design Value CB= 1699 + LiCB Prev +/- (10 + 126.3/laCBI) ppm (Design Conditions) CB= i?J')._ +/- 28 ppm Reference Technical Report NE-1197, Rev. O V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable Design Tolerance is met _x_ YES - - NO Acceptance Criteria is met : x YES NO VI Comments -aCB = -7 J 4 pcm/ppm LiCB Prev = (CB)MARO - 1876 ppm Prepared By: /~ -!J. ~ . Reviewed By: --6'-/_._.,,::J_._Pt,_;;;.~~____;;:_;;_-
NE-1206 S2C16 Startup Physics Tests Report . Page 45 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
HZP Boron Worth Coefficient Measurement Reference Proc No/ Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB: moving CC: 226 CD: 226 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (uF): S"'l 7. 3 Test Power Level (% F.P.): O Conditions SDA: 226 SDB: 226 CA: 226 Other (specify):
(Actual) CB: moving CC: 226 CD: 226 Below Nuclear Heating O.ate/ime /est Performed:
S ?.5 ff l{J.O Measured Parameter aCa; Boron Worth Coefficient (Description)
IV Test Results Measured Value aCa = - 7. 5'(, pcm/ppm Design Value aC 8 = -7.14+/-0.71 pcm/ppm (Design Conditions)
Reference Technical Report NE,-1197, Rev. O V FSAR/Tech Spec Not Applicable Acceptance Criteria Reference Not Applicable
)( YES Design Tolerance is met - - NO Acceptance Criteria is met : YvEs NO VI Comments Prepared By: f'! // ~ - - Reviewed By: _J'--._&ic..--
- _17l--=-~""---'-
NE-1206 S2C16 Startup Physics Tests Report Page 46 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Control Bank D Worth Measurement, Rod Swap Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditio"ns SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB: moving CC: 226 CD: moving Below Nuclear Heating .
111 Bank Positions (Steps) RCS Temperature (°F): ) YC *1 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: moving Cc: 226 CD: moving Below Nuclear Heating
- . Dat/.Ti~ Test Performed:
s* J.6 qf oo IJ..
Measured Parameter 10 Rs; Integral Worth of Control Bank D, (Description) Rod Swap RS
- IV Measured Value lo = /Of./'-1 (Adjusted Measured Test Critical Reference Bank Position = t 2'1 steps)
Results Design Value (Actual Conditions) 1/s= /0).0.)... (Adjusted Measured Critical Reference Bank Position = !J'I steps)
. Design Value (Design Conditions) 1/s= 1022 +/- 153 pcm (Critical Reference Bank Position= 176 steps)
Reference Engineering Transmittal NAF 99-0047, Rev. 0, VEP-FRD-36A FSAR/Tech Spec lf Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-36A Design Tolerance is met __L YES - - NO Acceptance Criteria is met : ....fL_ YES NO VI Comments Prepared By: ~/ d. Jn.it!M Reviewed By: / ,d_ ~
NE-1206 S2C16 Startup Physics Tests Report . Page 47 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Control Bank C Worth Measurement, Rod Swap Reference Proc No/ Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): 0 Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB: moving CC: moving CD: 226 Below Nuclear Heatinq II I Bank Positions (Steps) RCS Temperature (°F): SI./ 6,0 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: moving CC: moving CD: 226 Below Nuclear Heating Da!j~ime Test Performed:
.f ;J. t/ ff OOS'/
Measured Parameter leR5; Integral Worth of Control Bank C, (Description) Rod Swap IV Measured Value I C
RS_
q;s (Adjusted Measured Test Critical Reference Bank Position = / 6 2. steps)
Results Design Value (Actual Conditions) I C
RS_
ggo_ r .(Adjusted Measured Critical Reference Bank Position = /62 steps)
Design Value (Design Conditions) 1/s= 881 +/- 132 pcm (Critical Reference Bank Position = 151 steps)
Reference Engineering Transmittal NAF 99-0047, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance'is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-36A Design Tolerance is met t/ YES - - NO Acceptance Criteria is met : ~YES NO VI Comments Prepared By: p_(). ~- JJt;;lt,,, Reviewed By: I!. -LI. ~
NE-1206 S2C16 Startup Physics Tests Report Page 48 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Control Bank A Worth Measurement, Rod Swap Reference Proc No / Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: moving Other (specify):
(Desiqn) CB: moving CC: 226 CD: 226 Below Nuclear HeatinQ 111 Bank Positions (Steps) RCS Temperature (°F): S" lJ 6,6 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: 226 CA: moving Other (specify):
(Actual) CB: moving CC: 226 CD: 226 Below Nuclear Heating
, Date/Time Test Performed:
S/16/?f O !lS I
?,.
Measured Parameter IA Rs; Integral Worth of Control Bank A; (Description) Rod Swap IV Measured Value I RS_
A -
J_ol. (Adjusted Measured Test Critical Reference Bank Position = 62 steps}
Results Design Value (Actual Conditions) I RS_
A - I 19. O (Adjusted Measured Critical Reference Bank Position = C2 steps)
Design Value (Design Conditions) 1/s= 194 +/- 100 pcm (Critical Reference Bank Position = 58 steps)
Reference Engineering Transmittal NAF 99-0047, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-36A Design Tolerance is met V YES NO
-;T° YES Acceptance Criteria is met : NO VI Comments Prepared By: f °- }?zdt_. Reviewed By: t./J.~
NE-1206 S2C16 Startup Physics Tests Report Page 49 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Shutdown Bank B Worth Measurement, Rod Swap Reference Proc No/ Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: 226 SOB: moving CA: 226 Other (specify):
(Desiqn) CB: moving CC: 226 CD: 226 Below Nuclear Heatinq 111 Bank Positions (Steps) RCS Temperature (°F): ~1./7.,:2.
Test Power Level(% F.P.): O Conditions SDA: 226 SOB: moving CA: 226 Other (specify):
(Actual) CB: moving CC: 226 CD: 226 Below Nuclear Heating
-nate/Time Test Performed:
s-/Jo/ 11 0)2/
Measured Parameter 158 RS; Integral Worth of Shutdown Bank B, (Description) Rod Swap IV Measured Value lss RS
= I 13 3 (Adjusted Measured Test Critical Reference Bank Position = 2:i.. 6 steps)
Results Design Value RS (Actual Conditions) lss = !/fO,O (Adjusted Measured Critical Reference Bank Position = ;z?. 6 steps)
Design Value *
(Design Conditions) lss RS
= 1197 +/- 180 pcm (Critical Reference Bank Position =207 steps)
Reference Engineering Transmittal NAF 99-0047, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-36A Design Tolerance is met .~YES - - NO Acceptance Criteria is met : YES NO VI Comments Prepared By: , / _g_ JJ7;J!v, Reviewed By: /: 4. ~
NE-1206 S2Cl6 Startup Physics Tests Report Page 50 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND,EVAL_UATION SHEET I Test
Description:
Shutdown Bank A Worth Measurement, Rod Swap Reference Proc No/ Section: 2-NPT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): O Conditions SDA: moving SOB: 226, CA: 226 Other (specify):
(Desiqn) CB: moving CC: 226 CD: 226 Below Nuclear Heating Ill Bank Positions (Steps) RCS Temperature (°F): f; 'I(, P Test Power Level(% F.P.): 0 Conditions SDA: moving SOB: 226 CA: 226 Other (specify):
(Actual) CB: moving CC: 226 CD: 226 Below Nuclear Heating bate/Time Test Performed:
- S /J.t/ ff o]OS Measured Parameter lsAR5; Integral Worth of Shutdown Bank A, (Description) Rod Swap
= 901 RS IV Measured Value lsA (Adjusted Measured Test Critical Reference Bank Position = /60 steps)
Results Design Value (Actual Conditions) lsA RS
= q;s-. r (Adjusted Measured Critical Reference Bank Position = /oO steps)
Design Value RS (Design Conditions) lsA = 915 +/- 137 pcm (Critical Reference Bank Position = 157 steps)
Reference Engineering Transmittal NAF 99-0047, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Pesign Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance SNSOC may specify that additional testing Criteria be performed.
Reference VEP-FRD-36A Design Tolerance is met -
i/ YES - - NO Acceptance Criteria is met :
. t/- YES NO VI Comments Prepared By:
17 b *-~ Reviewed By: ~ .{}, ~
NE-1206 S2C16 Startup Physics Tests Report Page 51 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
Total Rod Worth, Rod Swap Reference Proc No/ Section: 2-N PT-RX-008 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (°F): 547 Test Power Level(% F.P.): o Conditions SDA: moving SOB: moving CA: moving Other (specify):
(DesiQn) CB: moving CC: moving CD: moving Below Nuclear Heating 111 Bank Positions (Steps) RCS Temperature (uF): S"'/7 Test Power Level(% F.P.): O Conditions SDA: moving SOB: moving CA: moving Other (specify):
(Actual) CB: moving CC: moving CD: moving Below Nuclear Heating CTa~fari ;;st Pert;;ii Measured Parameter lrora1: Integral Worth of All Banks, (Description) Rod Swap IV Measured Value lrc1a1= s-s30 pcm Test Results Design Value (Actual Conditions) lrc1a1= S' L/ 61 pcm Design Value (Design Conditions) lrc1a1= 5472 +/- 547 pcm Reference Engineering Transmittal NAF 99-0047, Rev. 0, VEP-FRD-36A FSAR/Tech Spec If Design Tolerance is exceeded, SNSOC shall V evaluate impact of test result on safety analysis.
Acceptance Additional testing must be performed.
Criteria Reference VEP-f RD-36A Design Tolerance is met v YES - - NO Acceptance Criteria is met : -;7 YES NO VI Comments Prepared By: L* 4. /JJ~ Reviewed By:
NE-1206 S2C16 Startup Physics Tests Report Page 52 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TESTRESULTS AND EVALUATION SHEET I Test
Description:
M/D Flux Map - At Power Reference Proc No / Section: 2-NPT-RX-008 ,002 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (uF): TREF +/- 1 Test Power Level(% F.P.):::; 30 Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB: 226 CC:
- CD:
- Must have 2:: 38 thimbles**
111 Bank Positions (Steps) RCS Temperature (°F):
Test Power Level(% F.P.): .2 _9 Td J, 2
Conditions SDA: 226 SOB: *226 CA: 226 Other (specify):
CD: /b2- -
(Actual) CB: 226 CC: ;226 4/ /Nn16fe J
- Date/Time Test Performed:
S-/.3o/f'9 . /;J...S-/
Maximum Relative Nuclear Enthalpy Total Heat Maxir:num Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P FL\H{N) Factor F0 {Z) Power Tilt Test Measured -.S:7 ~.I.~. 't Value 7,7 ,P ~ o,9
- .s;;.., ,2, 2 OL /, 62..0 I Results Design Value +/-10% for P; ~0.9 (Design +/-15% for P;<0.9 N/A N/A ~ 1.0203 Conditions) (P; = assy power)
Reference WCAP-7905, Rev. 1 None None WCAP-7905,Rev.1 NE-1197, Rev. 0 NE-1197,Rev. 0 V FSAR/COLR None Ft.H(N)i1 .56(1 +0.3(1-P)) Fa(Z)~4.64.K(Z) None Acceptance Criteria Reference None COLR 2.4 COLR2.3 None Design Tolerance is met . _LYES
- - NO Acceptance Criteria is met : /YES NO VI
- As required Comments ** Must have at least 16 thimbles for quarter core maps for multi-point calibrations Prepared B ~ c~ Reviewed By: &Q::::)+-\...6 L NE-1206 S2C16 Startup Physics Tests Report Page 53 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
MID Flux Map - At Power Reference Proc No I Section: 2-NPT-RX-008 ,002 Seauence Steo No:
II Bank Positions (Steps) RCS Temperature (°F): TREF +/- 1 Test Power Level(% F.P.): 65 s; P s; 75 Conditions SDA: 226 SDB: 226 CA: 226 Other (specify):
(Design) CB: 226 CC: 226 CD:
- Must have ~ 38 thimbles**
111 Bank Positions (Steps) RCS Temperature {aF): N .. .,_ 1.S:~?..
Test Power Level(% F.P.): ~; .1 ?.
Conditions SDA: 226. SDB: 226 CA: 226 Other (specify):
(Actual) CB: 226 CC: 226 CD: 18'?
Datef!ire,Iest Performed:
- ,. ~ JI 1 C, 'LO*. lL(
Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%DIFF Channel Factor Channel Quadrant IV (Description) (M-P)/P F.6.H(N) Factor F0 (Z} Power Tilt Test Results Measured.
Value
- ~
- '/. l r~ o. ~
P<.....o.,; /.Lf1'{ /.? (,O J.012 i
- Design Value +/-10% for P; ~0.9 (Design +/-15% for P;<0.9 NIA NIA .S 1.0203 Conditions) (P; = assy power) I Reference WCAP-7905, Rev. 1 None None WCAP-7905,Rev.1 NE-1197, Rev. 0 NE*1197,Rev. 0 V FSAR/COLR None Ft.H(N)~1.56(1 +0.3(1-P)) Fa(Z)~.32/P"K(Z) None Acceptance Criteria Reference None COLR 2.4 COLR2.3 None
' ~ YES Design Tolerance is met
-- NO Acceptance Criteria is met : ~YES NO VI
- As required Comments ** Must have at least 16 thimbles for quarter core ma.ps for multi-point calibrations Prepared By: __./W!-"--
__ 1Ji;I/
____ Reviewed 8 ~ C ~
NE-1206 S2CI6 Startup Physics Tests Report Page 54 of 55
SURRY POWER STATION UNIT 2 CYCLE 16 STARTUP PHYSICS TEST RESULTS AND EVALUATION SHEET I Test
Description:
MID Flux Map - At Power Reference Proc No I Section: 2-NPT-RX-008 ,002 Sequence Step No:
II Bank Positions (Steps) RCS Temperature (UF): TREF +/- 1 Test -z..2Cc Power Level(% F.P.): 95 ~ P ~ 100 Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Design) CB: 226 CC: 226 CD: . Must have> 38 thimbles-Ill Bank Positions (Steps) RCS Temperature (°F): U,,'-41 ,,.;.~L.
Test --z_ ~~ Power Level(% F.P.): '11.,-,,
Conditions SDA: 226 SOB: 226 CA: 226 Other (specify):
(Actual) CB: 226 CC; 226 CD:
- --* Datemme_T~;;erforrned: J Cl, & '<t c~Jt; Maximum Relative Nuclear Enthalpy Total Heat Maximum Measured Assembly Rise Hot Flux Hot Positive lncore Parameter Power%01FF Channel Factor Channel Quadrant IV (Description) (M-P)/P F~H(N) Factor Fc(Z) Power Tilt
(.,. 0 Z. .~f-.,, ').~
Test Results Measured Value -3'. 71c, Fa?. /J£, , /, 4*90 1., 0 s, i,OIZ,'7
/, Z 77c)
Design Value +/-10% for P; ~.9 (Design +/-15% for P;<0.9 NIA NIA ~ 1.0202 Conditions) (P 1 = a.ssy power)
Reference WCAP-7905, Rev. 1 None None WCAF'-7905,Rev. 1 NE-1197, Rev. o NE-1197,Rev. O V FSAR/COLR None FeiH(N):s1 .56(1 +0.3(1-P)) Fc~,32/?"K(Z) None Acceptance Criteria Reference None COLR 2.4 COLR2.3 None
/
~
Design Tolerance is met Acceptance Criteria is met :
-- NO NO VI
- As required Comments ... Must have at least 16 thimbles for quarter core maps for multi-point calibrations Prepared By: J~l.((/µV-- Reviewed By: 1Jl!J.6 NE-1206 S2Cl6 Startup Physics Tests Report Page 55 of 55
_ __j